신광사 CMYKT

신광사 CMYKT

Korean Third National Report under the Joint Convention on the Safety of

Spent Fuel Management and on the Safety of Radioactive Waste Management

Oct. 2008Ministry of Education, Science & Technology

Oct. 2

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e-Copies of this report are available from : Knowledge & Information Management Dept.Korea Institute of Nuclear Safety POB 114, Yuseong, Daejeon Korea 305-600 Email: k196yyh@kins.re.kr

http://www.mest.go.krhttp://www.kins.re.kr

http://www.khnp.co.krhttp://www.kaeri.re.kr

http://www.knfc.co.krhttp://www.kopec.co.kr

제3차「사용후핵연료 관리 및방사성폐기물 관리 안전 공동협약」에

대한 국가보고서

공동협약 의무사항 이행에 관한 국가보고서

2008. 10교육과학기술부

2008. 10제3차「사용후핵연료

관리및

방사성폐기물관리

안전공동협약」에

대한국가보고서

공동협약의무사항

이행에관한

국가보고서교

육과

학기

술부

국가보고서 전자사본 요청 :

전자도서관/지식정보실 한국원자력안전기술원대전광역시 유성우체국 사서함 114, 305-600 Email: k196yyh@kins.re.kr

http://www.mest.go.kr http://www.kins.re.kr

http://www.khnp.co.kr http://www.kaeri.re.kr

http://www.knfc.co.kr http://www.kopec.co.kr

교육과학기술부와 한국원자력안전기술원을 중심으로 구성된 방사성폐기

물안전협약 추진단이 이 국가보고서를 작성하였습니다. 이 보고서의 작성

에 참여하여 적극적으로 도움을 주신 기관은 아래와 같습니다.

교육과학기술부서울특별시 종로구 세종로 55, 정부중앙청사우편번호 110-760전화: +82-2-2100-6981http://www.mest.go.kr

한국원자력안전기술원대전광역시 유성구 과학로 34우편번호 305-338전화: +82-42-868-0295http://www.kins.re.kr

한국수력원자력주식회사서울특별시 강남구 영동대로 411우편번호 135-791전화: +82-2-3456-1520http://www.khnp.co.kr

한국원자력연구원대전광역시 유성구 대덕대로 1045우편번호 305-353전화: +82-42-868-8010http://www.kaeri.re.kr

한국전력기술주식회사경기도 용인시 기흥구 용구대로 257우편번호 446-713전화: +82-31-289-4774http://www.kopec.co.kr

한전원자력연료주식회사대전광역시 유성구 대덕대로 1047우편번호 305-353전화: +82-42-868-1627http://www.knfc.co.kr

중심단어: 방사성폐기물안전협약, 방사성폐기물관리, 사용후핵연료관리, 국가보고서, 국제안전체계, 원자력시설

ISBN 978-89-957325-9-5 93550 (Print, Korean)

ISBN 978-89-93507-11-9 93550 (Print, English)

ISBN 978-89-93507-10-2 98550 (e-book, Korean)

ISBN 978-89-93507-12-6 98550 (e-book, English)

머 리 말

2001년 6월 18일 발효된 “사용후핵연료 및 방사성폐기물 관리 안전 공동협

약”(이하 공동협약이라 한다)의 체약국으로서 2002년 9월 16일 비준서를 기탁한 대

한민국 정부는 공동협약의 제32조(보고)에 따라 체약국의 의무 이행현황을 기술한

제3차 국가보고서를 작성하였다.

이 국가보고서는 공동협약하의 국가보고서 형태 및 체계에 관한 지침에 따

라 작성되었으며 제 2차 검토회의 결과인 요약보고서의 권고사항을 반영하였다. 그

리고 제 2차보고서와 비교하여 변경된 부분은 볼드 및 이탤릭체로 기술하였다. 본

보고서는 협약의 조문배열을 토대로 조항별로 의무사항의 이행내용을 기술하는 체

계를 갖고 있다. 보고서의 내용은 따로 시점을 명기한 경우를 제외하고는 2007년

12월31일을 기준시점으로 하여 작성하였다.

이 국가보고서에서 다루고 있는 적용시설은 공동협약 제 2조 및 제 3조에

정의된 바와 같이 대한민국의 관할권 하에서 안전에 대한 고려가 요구되는 규모로

사용후핵연료 및 방사성폐기물의 취급, 처리, 저장 혹은 처분된 민간시설과 그 부

지, 건물, 장비들을 포함한다.

이 국가보고서는 교육과학기술부에 의해 구성된 공동협약이행을 위한 “추진

단” 및 추진단 산하 “작업반”에 의해 작성되었으며 정부, 학계, 연구소, 및 산업계

의 전문가들에 의해 검토되었다. 이후 원자력안전위원회 방사선방호분과에 상정되

어 보고되었다.

이 국가보고서의 작성에 기여한 주요 참여자는 다음과 같다: 교육과학기술

부의 문병룡, 구혁채, 박병현, 김재신; 한국원자력안전기술원의 윤철호, 석태원, 노병

환, 이윤근, 정재학, 김성일, 이관희, 육대식, 안상면, 정승영, 전제근, 김종래, 유송

재, 김석원, 장재권, 서보균, 이승행, 장기원, 우주희; 한국수력원자력(주)의 구권회,

박성철, 김경덕; 한국전력기술(주)의 조건택, 이병식; 한전원자력연료(주)의 조석주,

설증군, 류재봉; 한국원자력연구원의 정운수, 박진호.

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목 차

A. 서 문 ·························································································································1

B. 정책 및 관례 (제32조 1항) ·················································································5

B.1 국가 방사성폐기물 관리 정책 ···················································································5

B.1.1 국가정책 ···············································································································5

B.1.2 기본원칙 ···············································································································6

B.1.3 이행방안 ···············································································································6

B.2 사용후핵연료 관리 관례 ·····························································································8

B.2.1 발전시설 ···············································································································8

B.2.2 연구시설 ···············································································································8

B.3 방사성폐기물 관리 관례 ·····························································································9

B.3.1 발전시설 ···············································································································9

B.3.2 연구시설 ·············································································································10

B.3.3 핵연료가공시설 ·································································································11

B.3.4 방사성동위원소 폐기물 관리시설 ·································································12

B.4 방사성폐기물의 정의 및 분류에 사용되는 기준 ·················································13

C. 적용범위 (제3조) ··································································································15

C.1 공동협약 적용 방사성폐기물 ···················································································15

C.2 사용후핵연료의 재처리 ·····························································································16

C.3 천연방사성물질 ···········································································································16

C.4 군사․방위시설 발생 방사성폐기물 ·······································································16

D. 저장량 및 목록 (제32조 2항) ···········································································17

D.1 사용후핵연료 관리시설 ·····························································································17

D.1.1 발전시설 ············································································································17

D.1.2 연구시설 ············································································································18

D.2 방사성폐기물 관리 ·····································································································20

D.2.1 발전시설 ············································································································20

D.2.2 연구시설 ············································································································21

D.2.3 핵연료가공시설 ································································································21

D.2.4 방사성동위원소 폐기물 관리시설 ································································22

D.2.5 기타시설 ············································································································23

D.3 해 체 ·····························································································································23

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D.3.1 연구용원자로 1, 2호기 ···················································································23

D.3.2 우라늄 변환 시설 ····························································································24

D.4 기록관리 및 확인 ·······································································································25

E. 법규 및 규제체계 ································································································27

E.1 이행 조치 (제18조) ·····································································································27

E.2 법규 및 규제체제 (제19조) ·······················································································27

E.2.1 입 법 ···················································································································28

E.2.2 원자력 규제체계 ·······························································································36

E.2.3 인․허가 절차 및 안전성 평가 ·····································································37

E.2.4 규제검사 ·············································································································38

E.2.5 집행 ·····················································································································40

E.2.6 단계별 책임소재 ·······························································································41

E.2.7 규제해제 ·············································································································41

E.3 규제기관 (제20조) ·······································································································43

E.3.1 규제기관의 권한 및 책임 ···············································································43

E.3.2 규제기관 및 지원기관의 조직 및 자원 ·······················································44

E.3.3 규제의 독립성 ···································································································50

F. 일반 안전 규정 ·····································································································53

F.1 허가소지자의 책임 (제21조) ·····················································································53

F.1.1 허가소지자의 책임이행 보장조치 ·································································53

F.1.2 최종 책임 ···········································································································54

F.2 조직․인력 및 재원 (제22조) ···················································································55

F.2.1 발전시설 ·············································································································55

F.2.2 연구시설 ·············································································································57

F.2.3 핵연료가공시설 ·································································································59

F.2.4 방사성동위원소 폐기물 관리시설 ·································································60

F.2.5 처분시설 폐쇄 후 관리재원 확보 ·································································62

F.3 품질보증 (제23조) ·······································································································63

F.3.1 품질보증 정책 ···································································································63

F.3.2 품질보증계획서 ·································································································63

F.3.3 품질보증계획 이행 및 평가 ···········································································64

F.3.4 규제 관리활동 ···································································································65

F.4 운영 방사선방호 (제24조) ·························································································67

F.4.1 규정 및 요건 ·····································································································67

F.4.2 원자력이용시설의 관리 단계별 방사선방호 체계 ·····································70

- iii -

F.4.3 원자력이용시설의 배출 제한 체계 ·······························································74

F.4.4 원자력이용시설에서 비계획/비관리 배출의 경우 보완대책 이행체계 ·75

F.5 비상대책 (제25조) ·······································································································78

F.5.1 규정 및 요건 ·····································································································78

F.5.2 국가 방사능재난관리 체계 ·············································································78

F.5.3 방재대책 교육 및 훈련 ···················································································80

F.5.4 인접국과의 협정을 포함한 국제협정 ···························································81

F.6 해체 (제26조) ···············································································································83

F.6.1 규정 및 요건 ·····································································································83

F.6.2 인력 및 재원 ·····································································································84

F.6.3 방사선 방호 ·······································································································85

F.6.4 비상 대책 ···········································································································85

F.6.5 기록 관리 ···········································································································86

G. 사용후핵연료 관리 안전 ···················································································87

G.1 일반 안전 요건 (제4조) ····························································································87

G.1.1 설계기준 및 요건 ····························································································87

G.1.2 고려해야 할 요건 ····························································································89

G.2 기존 시설 (제5조) ······································································································90

G.3 제안된 시설의 부지선정 (제6조) ············································································91

G.4 시설의 설계 및 건설 (제7조) ··················································································92

G.5 시설의 안전성 평가 (제8조) ····················································································93

G.6 시설의 운영 (제9조) ··································································································94

G.6.1 기술기준 ············································································································94

G.6.2 운전 제한조건 설정 ························································································95

G.6.3 시설의 운영절차 ······························································································95

G.6.4 공학적 기술 지원 ····························································································95

G.6.5 이상사태의 보고 및 기록관리 ······································································95

G.6.6 해체계획 수립, 보완 및 규제기관 검토절차 ·············································96

G.6.7 비상계획 ············································································································96

G.7 처분 (제10조) ··············································································································97

H. 방사성폐기물 관리 안전 ···················································································99

H.1 일반 안전 요건 (제11조) ··························································································99

H.1.1 설계기준 및 요건 ··························································································99

H.1.2 고려해야 할 요건 ··························································································102

H.2 기존시설 및 과거관행 (제12조) ············································································104

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H.3 제안된 시설의 부지선정 (제13조) ········································································106

H.3.1 부지선정을 위한 인자 ··················································································106

H.3.2 방사성폐기물 처분시설 인․허가 ······························································109

H.3.3 처분시설 부지선정 현황 ··············································································110

H.4 시설의 설계와 건설 (제14조) ················································································112

H.4.1 설계시 고려인자 ····························································································112

H.4.2 건설시 고려인자 ····························································································118

H.5 시설의 안전성 평가 (제15조) ················································································119

H.5.1 안전성평가 및 방사선환경영향평가 ··························································119

H.5.2 안전성평가의 갱신 및 안전성 재평가 ······················································121

H.6 시설의 운영 (제16조) ······························································································123

H.6.1 허가기준 및 운영 중 관리기준 ··································································123

H.6.2 처분시설 운영 안전관리 ··············································································125

H.6.3 운전 제한조건 설정 ······················································································126

H.6.4 시설의 운영절차 ····························································································126

H.6.5 공학적 기술 지원 ··························································································127

H.6.6 방사성폐기물 특성평가 및 분류절차 ························································127

H.6.7 이상사태의 보고 및 기록관리 ····································································128

H.6.8 해체계획 수립, 보완 및 규제기관 검토절차 ···········································129

H.6.9 폐쇄계획 수립, 보완 및 규제기관 검토절차 ···········································129

H.6.10 운전경험 분석 및 반영을 위한 절차 ······················································130

H.7 폐쇄 후 제도상 조치 (제17조) ··············································································131

H.7.1 기록의 보존 ····································································································131

H.7.2 제도적 관리 ····································································································132

H.7.3 방사성물질 유출시 개입조치 ······································································133

I. 국경간 이동 (제27조) ·························································································135

I.1 국내 운반규정 ············································································································136

I.2 안전요건 ······················································································································136

I.2.1 일반 안전요건 ··································································································136

I.2.2 운반용기 안전요건 ··························································································136

I.2.3 운반 안전요건 ··································································································137

I.3 승인 및 행정조치 ······································································································137

I.3.1 설계 승인 ··········································································································137

I.3.2 운반용기 승인 ··································································································137

I.3.3 특별 승인 ··········································································································138

I.3.4 운반사례 ············································································································138

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J. 폐기밀봉선원 (제28조) ······················································································139

J.1 관리체계 ······················································································································139

J.2 폐기 밀봉선원의 관리 ······························································································140

J.2.1 시설 및 취급요건 ····························································································140

J.2.2 관 리 ··················································································································140

J.2.3 반 환 ··················································································································141

K. 안전성 증진 계획 ······························································································143

K.1 경주 처분시설의 장기안전성 증진을 위한 단계별 접근 ·································143

K.2 사용후핵연료 안전성 증진을 위한 연구개발계획 수립 ···································144

K.3 방사성폐기물 관리법 제정 ·····················································································146

K.4 생활주변방사선관리법(안) 추진 ············································································146

K.5 폴리머고화 기술 적용 ·····························································································147

부 록 ·························································································································149

부록 A. 사용후핵연료 관리시설 목록 ·········································································151

부록 B. 방사성폐기물 관리시설 목록 ·········································································153

부록 C. 해체중인 원자력시설 목록 ·············································································157

부록 D. 원자력안전헌장 ·································································································158

부록 E. 원자력안전정책성명 ·························································································159

부록 F. 방사성폐기물 관련 교육과학기술부고시 ······················································165

부록 G. 참고 자료 ···········································································································169

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표 목 차

표 D.1-1 발전용 원자로 사용후핵연료 저장량 ·································································18

표 D.1-2 연구시설 내 사용후핵연료 저장량 ·····································································19

표 D.2-1 발전용원자로 방사성폐기물 저장현황 ·······························································20

표 D.2-2 연구시설 방사성폐기물 저장현황 ·······································································21

표 D.2-3 핵연료가공시설 방사성폐기물 저장현황 ···························································22

표 D.2-4 방사성동위원소 폐기물 저장현황 ·······································································23

표 D.3-1 연구용원자로 해체폐기물 저장현황 ···································································24

표 D.3-2 우라늄변환시설 해체폐기물 저장현황 ·······························································24

표 E.2-1 원자력 관련 법률 ···································································································29

표 E.2-2 폐기시설 관련 교육과학기술부고시 ···································································33

표 F.4-1 선량한도 ····················································································································68

표 F.4-2 원전의 액체 및 기체 방사성폐기물 연간배출량 및 주민방사선량 ··············76

표 F.4-3 대덕부지 방사성폐기물 연간배출량 및 주민방사선량 ····································77

표 H.3-1 부지선정을 위한 주민투표 결과 ·······································································111

표 K.5-1 폴리머 고화체에 대한 성능시험 결과 ·····························································148

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그 림 목 차

그림 A.1-1 주요 방사성폐기물 발생원 및 관리시설의 위치와 운영현황 ·····················3

그림 E.2-1 원자력 법령 체계 ·······························································································30

그림 E.2-2 원자력법 구성 체계 ···························································································31

그림 E.2-3 전기사업법령 체계 ·····························································································34

그림 E.2-4 원자력 관련 정부조직 ·······················································································36

그림 E.2-5 원자력 안전규제 체제 ·······················································································37

그림 E.2-6 폐기시설등의 인·허가 절차 ··············································································39

그림 E.3-1 교육과학기술부 조직 ·························································································47

그림 E.3-2 원자력안전위원회 구성 체계 ···········································································49

그림 E.3-3 한국원자력안전기술원 조직 ·············································································51

그림 F.2-1 한국수력원자력(주) 원자력 관련 조직 ···························································56

그림 F.2-2 발전용 원자로시설 운영 조직 ··········································································56

그림 F.2-3 한국원자력연구원 방사성폐기물 관리 관련 조직 ········································58

그림 F.2-4 한전원자력연료(주) 조직 ·················································································60

그림 F.2-5 원자력발전기술원 조직 ······················································································61

그림 F.5-1 방사능방재조직 체계 ··························································································80

그림 H.3-1 중·저준위 방사성폐기물 처분시설 부지선정 절차 ···································111

그림 H.4-1 월성원자력환경관리센터 조감도 ···································································113

그림 H.4-2 지하시설 단면도 ·······························································································113

그림 H.4-3 설계 단계별 연관관계 ···················································································116

그림 H.4-4 주요 기술분야별 연관관계 ···········································································116

그림 J.2-1 방사성동위원소 폐기물의 관리 체계 ···························································141

그림 K.1-1 원자력법에 따른 방사성폐기물 처분시설에 대한 단계별

안전규제 체계 ··································································································143

그림 K.2-1 사용후핵연료 연구개발 종합 Action Plan ·················································145

- 1 -

A. 서 문

대한민국 정부는 국가 에너지자원이 불충분한 여건 하에서 원자력발전사업

을 촉진함으로써 안정적인 에너지 공급을 위한 일관된 국가 정책을 유지하여 왔으

며, 현재 원자력발전에 의한 전력발전량은 전체의 약 40%정도를 차지하고 있다.

1978년 최초로 고리원자력발전소 1호기의 상업운영이 개시된 이래 2007년

말 기준으로 20기의 원자력발전소가 운영되고 있으며, 운영 중인 원자력발전소 중

4기는 월성부지의 가압중수로이고, 고리, 영광, 울진부지에 위치한 다른 16기의 원

자력발전소는 가압경수로이다. 6기의 원자력발전소(OPR1000 4기, APR1400 2기)가

추가 건설 중이고, 2기가 계획단계에 있다.

2008년 8월 정부는 2030년까지 석유 등 화석에너지 의존도를 대폭 줄이

고 재생에너지의 이용을 4배 이상 확대하기로 했다. 이에 따라, 현재 14.9%인 원

자력에너지의 비중은 2030년까지 27.8%로 증가될 것으로 예상 된다. 원자력에너

지의 설비 비중은 현재 26%에서 41%, 발전량 비중은 현재 36%에서 59%로 각각

증가 될 것이고, 이를 위해 10기의 원전을 신규로 건설할 방침이다.

IAEA는 2008년 6월 개최된 IAEA 정기이사회에서 우리나라에 대한 ‘포괄

적 결론’을 승인함으로써 핵 투명성을 공식 인정 하였다.

한국원자력안전기술원은 안전규제기술과 경험을 국제사회와 공유하기

위해 국제원자력안전학교를 2008년 1월 개교하였으며, IAEA와 “원자력안전협력

약정”을 체결하여 IAEA 아시아 지역훈련센터의 기능도 수행하는 등 원자력관련

국제사회에서 선도그룹으로 성장하였다.

운영 중 원전에서 발생하는 사용후핵연료는 부지 내의 습식저장시설 및 건

식저장시설(가압중수로에 한함)에 저장되어 있으며, 이들 원전에서 발생한 중․저준위방사성폐기물은 원전 부지내의 저장시설에 저장되어 있다.

현재 대전의 한국원자력연구원에 1기의 연구용원자로(하나로)가 1995년부터

운영 중에 있으며 열출력이 30 MW이다. 서울의 전 한국원자력연구원 부지에 위치

한 연구로 1, 2호기는 가동중지 후 원자로 및 보조시설은 해체가 진행 중이다.

- 2 -

국내 원자력발전소의 핵연료는 대전에 있는 한전원자력연료(주)에서 가공생

산하고 있으며, 가공공정 동안 발생하는 방사성폐기물은 자체저장고에 저장되어 있

다. 또한 의료, 연구 및 산업체에서 방사성동위원소 등 이용기관은 꾸준히 증가하

여 2007년 말 기준으로 약 3500개에 달하며, 이러한 기관은 전국에 걸쳐 널리 분포

하고 있고 다양한 형태의 방사성폐기물이 발생되고 있다. 방사성동위원소폐기물은

대전에 위치한 한국수력원자력(주) 원자력발전기술원의 관리시설에서 안전하게 저장

되고 있다.

1980년대 초부터 정부는 방사성폐기물의 안전한 관리를 위하여 처분부지 확

보를 위한 지속적인 대책을 강구하여 왔다. 1998년 9월 30일에 개최된 제 249차 원

자력위원회에서 2008년까지 중․저준위 방사성폐기물 처분장, 2016년까지 중앙집중식 사용후핵연료 중간저장시설의 건설․운영을 목표로 하는 “국가 방사성폐기물 관리대책”을 결정하였으나 부지선정에 많은 어려움이 있었다. 이에 따라 2004년 12월 17

일에 개최된 제 253차 원자력위원회에서 2008년까지 중․저준위 방사성폐기물 처분시설의 건설․운영을 우선 시행하고 사용후핵연료는 국가정책방향, 국내외 기술개발 추이 등을 감안하여 중간저장시설 건설 등을 포함한 관리방침을 추후 검토하여 결정하기

로 하였다.

정부는 2005년 6월 중·저준위 방사성폐기물 처분시설 후보부지 선정 등

을 공고하였고, 부지적합성 평가, 주민투표 등 공고에 명시된 절차에 따라 2005

년 11월 경주시를 최종후보부지로 선정하였다. 2006년 6월 처분방식선정위원회

는 1단계 처분방식을 동굴처분으로 결정하였다. 한국수력원자력(주)는 2007년 1

월 교육과학기술부에 중·저준위 방사성폐기물 처분시설 건설·운영 허가 신청서

를 제출하였다. 한국원자력안전기술원은 이들 관련 신청서에 대한 안전심사를

수행하였고, 교육과학기술부는 2008년 7월 31일 건설·운영허가를 발급하였다. 현

재 한국수력원자력(주)는 허가받은 바에 따라 중·저준위 방사성폐기물 처분시설

을 건설하고 있다.

현재 우리나라의 원자력시설 및 방사성폐기물 관리시설의 현황은 그림

A.1-1과 같다.

- 3 -

울릉도

독도

°

•대전•대전□△△ KNF□●●△◇ KAERI△ NETEC

•서울

동해

•광주

부산 •

서해울진■■■■■■ ●●●●●● ▲▲

월성 ■■■■ ●●●● ▲○★

고리 ■■■■ ●●●● ▲▲▲▲

■■■■■■ 영광●●●●●●▲▲

제주도

◆◆ (구)KAERI

■ 발전용원자로

□ 연구로/기타 원자력시설

● 사용후핵연료저장시설(습식)

○ 사용후핵연료저장시설(건식)

▲ 원자력발전소폐기물저장시설

△ 기타 원자력시설폐기물저장시설

◆ 연구용원자로시설 해체

◇ 기타 원자력시설 해체

★ 중·저준위방사성폐기물 처분시설

그림 A.1-1 주요 방사성폐기물 발생원 및 관리시설의 위치와 운영현황

(2008. 10월 현재)

- 5 -

공동협약 제 32 조 보고

1. 제30조의 규정에 따라, 각 체약당사자는 국가보고서를 각 체약당사자 검토회의에

제출한다. 이 보고서는 이 협약의 의무를 이행하기 위하여 취해진 조치를 포함한

다. 또한 각 체약당사자별 보고서는 다음을 포함한다.

가. 사용후핵연료 관리 정책,

나. 사용후핵연료 관리 관례,

다. 방사성폐기물 관리 정책,

라. 방사성폐기물 관리 관례,

마. 방사성폐기물을 정의하고 구분하는데 사용되는 기준.

B. 정책 및 관례 (제32조 1항)

B.1 국가 방사성폐기물 관리 정책

B.1.1 국가정책

우리나라는 1998년 9월 30일 제249차 원자력위원회에서 “국가 방사성폐기물

관리대책”을 의결하여 방사성폐기물관리에 대한 기본방침을 확정하였다. 이는 그간

의 경험을 바탕으로 방사성폐기물 처분시설 부지 선정과정에서부터 안전성확보를

추구하는 정부의 의지에 대한 국민의 이해를 도모하고 부지선정 과정의 투명성을

강조하고 있는 것이다. 그 내용을 요약하면 다음과 같다.

1) 국가 책임 하에 관리

- 방사성폐기물은 장기간에 걸친 안전한 관리가 필요하므로 국가의 책임 하

에 관리한다.

2) 안전성을 최우선적으로 고려

- 방사성폐기물을 생태적․환경적으로 안전하게 관리하여 국민건강과 환경에 대한 위해를 방지하고, 방사성폐기물 안전관리에 관한 국제규범을 준수한다.

3) 폐기물 발생량을 최소화

- 원자력발전 및 방사성동위원소 이용에 수반되는 방사성폐기물의 발생량을

- 6 -

최소화한다.

4) 소요비용은 발생자가 부담

- 방사성폐기물 관리에 소요되는 비용은 발생시점에서 발생자가 부담하여 다

음 세대로의 부담전가를 지양한다.

5) 국민의 신뢰 하에 추진

- 투명하고 공개적인 방사성폐기물 관리로 대 국민 이해 및 신뢰도를 증진하

고, 관리사업은 지역사회와의 조화 및 지역발전에 기여하는 방향으로 추진

한다.

B.1.2 기본원칙

중․저준위 방사성폐기물 처분시설을 적기에 확보하기 위하여 2004년 12월 17일 제 253차 원자력위원회에서는 중․저준위 방사성폐기물 처분시설 우선 건설 추진, 부지확보 절차의 민주성과 투명성 제고, 유치지역 지원의 법제화 등을 포함한 “방

사성폐기물 관리대책” 계획을 아래와 같이 변경하였다.

1) 중‧저준위 방사성폐기물은 원자력발전소 부지 내 및 동위원소폐기물 저장시설 등에서 관리한 후, 천층방식 또는 동굴방식의 처분시설에 영구 처분하며, 단수

또는 복수의 중․저준위 방사성폐기물 영구처분시설의 건설을 우선 추진하여 2008년까지 완공한다.

2) 사용후핵연료는 국가정책방향, 국내외 기술개발 추이 등을 감안하여 관리방침을

추후 검토하여 결정한다.

B.1.3 이행방안

관리 조직

방사성폐기물을 안전하고 효율적으로 관리하기 위하여 지식경제부는 책임행정청

으로서 방사성폐기물의 저장․처리 또는 처분에 관한 기본정책 및 사업계획 등을 포함한 관리대책을 수립하고 원자력위원회의 심의․의결을 거쳐 시행한다. 원자력

- 7 -

발전사업자 또는 특별법에 의하여 설립되어 원자력발전관련 업무를 수행하는 법

인 중 지식경제부 장관이 지정하는 자는 대통령령이 정하는 방법 및 절차에 따라

방사성폐기물을 발생자로부터 인수하여 저장․처리 또는 처분하는 방사성폐기물관리사업을 수행한다.

규제 및 기술 기준

교육과학기술부 및 한국원자력안전기술원은 사용후핵연료 및 방사성폐기물 안전

관리에 관한 규제 및 기술기준을 개발한다. 사용후핵연료 및 방사성폐기물의 규

제 및 기술기준은 국제원자력기구에서 제정한 안전에 관한 기본 원칙, 원리, 지침

을 포함하는 국제규범을 준용한다.

사용후핵연료 중간저장시설

사용후핵연료는 원자력발전소 부지 내 임시 저장능력을 확장하여 2016년까지 각

원자력발전소 부지 내에서 관리하며, 중간저장시설 건설 등을 포함한 종합적인

관리방침은 충분한 논의를 거쳐 국민적 공감대 하에서 추진하되, 원자력발전소

부지 내의 임시저장시설이 2016년부터 포화되는 점을 감안하여 적기에 추진방침

을 결정할 예정이다.

중․저준위 방사성폐기물 처분시설정부는 2004년 12월 제 253차 원자력위원회에서 처분규모는 1단계 10만드럼

규모로 건설하며, 단계적으로 증설하여 총 80만 드럼 규모로 건설키로 하였

다. 처분방식은 부지여건에 따라 천층처분 또는 동굴처분 방식을 결정하기로

하였다.

2005년 3월 31일 중․저준위 방사성 폐기물 처분시설에 대한 사회적 수용성을

제고하기 위하여 「중․저준위 방사성 폐기물 처분시설의 유치지역 지원에 관한

특별법」이 제정․공포되었다. 이 법률에 규정된 바에 따라 지식경제부장관은

사회 각계의 민간전문가 17인으로 구성된 부지선정위원회를 운영하여 유치지역

선정 계획, 부지조사 결과, 부지 선정과정 등을 공개적으로 진행하고 해당 지역

주민을 대상으로 설명회와 토론회를 실시하는 등 부지선정 절차 전반을 공정하

고 투명하게 추진하였다. 부지선정 절차에 따른 유치신청 지방자치단체에 대

하여 주민투표 실시결과 경주시가 최종후보부지로 선정되었다. 최종후보부지

는 총 80만드럼을 처분할 수 있는 규모로써 1단계 건설은 10만드럼 규모의 동

- 8 -

굴처분방식으로 결정되었다. 경주처분장은 “월성원자력환경관리센터”로 명명

되었다.

방사성폐기물 관리비용

방사성폐기물 관리비용은 발생자 부담원칙에 따라서 원자력발전사업자가 처분에

소요되는 비용을 사후처리충당금으로 충당하고, 원자력발전사업자 이외의 사업자

는 방사성폐기물관리사업자에게 방사성폐기물을 인도할 때 관리비용을 납부한다.

B.2 사용후핵연료 관리 관례

B.2.1 발전시설

원자력발전소에서 생성된 사용후핵연료는 원자력발전소 부지 내에서 저장․관리되고 있으며, 제 249차 및 제 253차 원자력위원회 의결에 따라 국가가 건설하고

자 하는 소외 중간저장시설 건설 일정과 연계해서 원자력발전소 부지 내 사용후핵

연료 저장시설의 저장용량을 확장하고 있다. 경수로형 원자력발전소의 경우 저장용

량의 확장을 위해 조밀저장대의 설치를 추진하여, 고리 원자력발전소 3호기, 울진

원자력발전소 1,2호기는 조밀저장대로의 교체를 완료하였으며, 2006년에는 고리 원

자력발전소 4호기, 영광 원자력발전소 3,4호기의 조밀저장대 교체를 완료하였으

며, 2008년 12월 말까지 울진 원자력발전소 3,4호기 조밀저장대 교체사업이 진행

될 예정이다. 고리 원자력발전소 1,2호기의 경우에는 저장능력이 부족하여 사용후

핵연료를 고리 원자력발전소 3,4호기 사용후핵연료 저장조로 이송하여 공동 저장

관리하고 있다. 중수로형인 월성 원자력발전소 1,2,3,4호기의 경우에는 소내 저장능

력의 확장을 위해 부지 내에 건식저장시설을 건설하여 운영하는데, 2006년 11월에

캐니스터 100개를 추가 건설하여 총 3,061 MTU 용량의 300개의 캐니스터가 운

영 중이며, 2009년 9월까지 7개 모듈 총 3,175 MTU 용량의 조밀건식저장시설을

추가로 건설할 계획이다.

B.2.2 연구시설

연구로 1,2호기 (KRR-1&2)

연구로 1,2호기 해체 사업이 착수됨에 따라 저장 중이던 사용후 핵연료봉 299개

모두를 1998년 6월에 미국으로 모두 반송하였다

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하나로 연구용 원자로

하나로 연구용 원자로에는 하나로에서 발생하는 사용후핵연료 20년분을 저장할

수 있는 사용후핵연료 저장 수조가 있다. 하나로 사용후핵연료 저장조는 하나로

에서 발생한 사용후핵연료 및 하나로에서 연소 실험을 마친 조사 시험용 핵연료

를 저장하도록 되어있다.

조사후연료시험시설

조사후연료시험시설은 가압경수로형 핵연료 집합체를 최대 20다발까지 저장할

수 있는 수조 설비를 갖추고 있다. 현재 저장수조에는 조사후시험을 목적으로

상용 원전으로부터 이송된 사용후핵연료가 저장되어 있다. 조사후시험은 핫셀

내에서 이루어지며 시험 과정에서 발생한 연료봉 절편들은 절편저장용기 (rod

cuts container)에 넣어 사용후핵연료 저장수조에 보관한다.

B.3 방사성폐기물 관리 관례

B.3.1 발전시설

기체 방사성폐기물 관리

기체방사성폐기물은 발전용 원자로의 운영 중 계통의 탈기 또는 누출로 인해 주

로 발생된다. 계통 탈기과정에서 발생된 기체방사성폐기물은 감쇠탱크 또는 활성

탄 지연대를 이용하여 방사능을 저감시킨 후 배출전 또는 주기적으로 시료채취

및 방사능 분석을 수행하며, 배출 시에는 연속 유출물 방사선감시기를 통해 대기

로 배출된다. 한편 건물 내 주요계통에서 누출된 기체방사성폐기물은 환기계통

의 고효율입자여과기 및 활성탄 여과기로 처리한 후, 연속 유출물 방사선감시기

를 거쳐 대기로 배출된다. 대기로 배출되는 기체유출물의 방사능은 제한구역경

계에서 교육과학기술부고시에 규정된 배출관리기준 이내로 제한되고 있으며, 시

설 운영자는 환경으로 배출되는 기체유출물에 의한 예상 주민피폭선량을 주기적

으로 평가하여 규제기관에 보고하고 있다.

액체방사성폐기물 관리

액체방사성폐기물은 원자로냉각재 및 관련 계통의 수질 정화 및 정비작업 등의

- 10 -

과정에서 주로 발생된다. 일반적으로 액체방사성폐기물은 증발기, 탈염기, 여과

기 등 처리계통에서 방사성물질이 제거된다. 배출 전에 방사능을 측정하여 제한

치를 만족할 경우 연속 유출물방사선감시기로 감시하면서 바다로 배출된다. 배

출되는 액체유출물의 방사능농도는 교육과학기술부고시에 규정된 배출관리기준을

만족되어야 한다. 시설 운영자는 환경으로 배출되는 액체유출물에 의한 예상 주

민피폭선량을 매분기 평가하여 규제기관에 보고하고 있다.

고체 방사성폐기물 관리

고체방사성폐기물은 시설의 정비 및 보수과정에서 발생되는 잡고체 폐기물 (기기

부품, 제염지, 작업복, 장갑, 신발 등)과 액체 및 기체방사성폐기물을 처리하는 과

정에서 농축폐액, 폐수지, 폐필터 등이 발생하고 있다. 잡고체 폐기물은 일반 압

축기 (10～30톤 용량)로 압축하여 포장하고 있다. 과거에는 농축폐액 및 폐수지를

주로 시멘트로 고화하였으나 현재 발전용 원자로에서 발생되는 농축폐액은 건조

설비에서 완전 건조시킨 후 파라핀으로 안정화하며, 폐수지는 폐수지 건조설비에

서 건조한 후 고건전성 용기 또는 이에 준하는 용기를 사용하여 포장하고 있다.

한편 폐필터는 적절한 차폐용기에 포장하여 저장한다.

B.3.2 연구시설

한국원자력연구원에는 방사성물질을 취급하는 시설로서 하나로시설, 조사후연

료시험시설, 동위원소생산시설, 조사재시험시설, 연구로용 핵연료 가공시설, 기타 실

험실들이 있다. 또한, 방사성폐기물 관리시설로는 방사성폐기물 처리시설과 저장시

설이 운영되고 있다.

기체 방사성폐기물 관리

방사성물질을 취급하는 시설의 환기계통에는 여과기가 설치되어 있어 방사성 기

체가 여과기에서 충분히 여과된 후에 대기로 배출하게 되어있다. 최종 배출구인

굴뚝에는 공기감시기가 설치되어 연속적으로 기체배출을 감시하고 있으며 기준

초과 시 배기를 중지함으로써 외부로 배출된 방사성물질에 의한 주민피폭선량이

관리목표치를 초과하지 않도록 운영하고 있다.

액체 방사성폐기물 관리

- 11 -

한국원자력연구원의 각 시설로부터 발생되는 액체폐기물은 각 시설내의 수집 탱

크에서 수집한 후 증발농축공정설비로 이송하여 처리되는데 응축수는 자연증

발시설에서 증발처리 되고 잔류분은 아스팔트 고화처리된다. 따라서 주변 환

경으로 배출되는 액체폐기물은 없다.

고체 방사성폐기물 관리

각 시설로부터 발생하는 사용후핵연료를 제외한 고체 방사성폐기물은 방사성폐기

물 처리시설 및 저장시설로 운반되어 일괄 처리하고 있다. 내부규정에 따라 방

사선량률 준위가 높은 고체 방사성 폐기물은 50리터 스테인리스 드럼에 포장되어

충분한 차폐능을 가진 콘크리트 구조물내에 보관하고 있으며, 방사선량률 준위가

낮은 저준위 방사성폐기물은 압축하여 200리터 드럼에 포장하여 저장고에 보관하

고 있다. 방사성폐기물의 저장 안전성 증진을 위하여 방사성폐기물 저장고에

모니터링 카메라를 설치하였다. 설치된 카메라는 방사성폐기물처리시설에서

원격으로 조정이 가능하여 이상이 발생할 경우 즉각적인 인지가 가능하도록

하였다.

B.3.3 핵연료가공시설

기체 방사성폐기물 관리

기체폐기물은 환기계통의 여과기를 거쳐 방사성물질을 제거한 후 굴뚝을 통하여

외부로 배출하며, 기체유출물 내의 방사능 배출량을 연속적으로 측정하여 기준

초과시 배기를 중지함으로써 외부로 배출된 방사성물질에 의한 주민피폭선량이

관리목표치를 초과하지 않도록 운영하고 있다.

액체 방사성폐기물 관리

액체폐기물은 경수로 연료 제조 공정에서 발생되는 폐수 및 중수로 연료 제조 공

정에서 발생되는 폐수 등 2가지로 구분하여 수집한다. 수집된 폐수는 그 특성에

따라 석회침전, 고분자 응집 및 원심분리 등의 방법을 이용하여 처리한다. 처리

후 액체폐기물 배출 기준치를 만족함을 확인한 후 방류하며, 환경으로 배출되는

액체유출물의 방사능이 제한구역경계에서 교육과학기술부고시에 규정된 배출관리

기준을 만족하도록 관리하며 액체폐기물의 배출량, 방사능량 및 방사능 농도 등

을 기록․관리한다. 고체 방사성폐기물 관리

- 12 -

핵연료가공시설에서 발생되는 고체폐기물은 주로 작업복, 장갑 등의 방호용품과

시설 보수시 발생하는 금속류, 액체폐기물 처리시 발생되는 석회침전물 등이며,

이는 종류별로 잡고체, 금속물, 합성물, 석회침전물, 목재류, 유리류 등으로 구분

하여 200리터 드럼에 담아 포장한다. 포장된 드럼은 드럼내의 방사능량, 폐기물

무게, 드럼의 표면오염도 및 방사선량 등을 측정하여 폐기물 저장시설에 보관하

고 있다.

B.3.4 방사성동위원소 폐기물 관리시설

방사성동위원소 이용기관은 개봉선원과 밀봉선원의 형태로 방사성동위원소를

이용하고 있다. 개봉선원 폐기물은 가연성, 비가연성, 비압축성, 폐필터, 동물사체,

유기폐액, 무기폐액 등으로 세분되고 있으며, 이들은 한국수력원자력(주)의 원자력발

전기술원에 인도되고 있다.

방사성동위원소 이용기관에서 발생된 폐기물 중 개봉선원 폐기물은 한국동위

원소협회가 수거하여 원자력발전기술원에 인도하고 밀봉선원 폐기물은 발생기관이

직접 또는 대행기관을 통하여 원자력발전기술원에 인도되고 있다. 원자력발전기술

원은 방사성동위원소 폐기물을 방사성동위원소 폐기물 관리시설에 안전하게 저장관

리하고 있다.

방사성동위원소 폐기물 관리시설의 저장효율을 향상시키기 위하여 저장중인

일부 방사성동위원소 폐기물에 대하여 감용 처리를 하고 있다. 유리류 등의 비가연

성 폐기물은 압축기를 사용하여 압축 처리하고 가연성폐기물과 유기폐액은 소각처

리 하고 있다. 일부 밀봉선원 폐기물은 저장효율을 향상시키기 위하여 선원부분을

분리한 후 집중저장용기에 저장하고 있다.

- 13 -

B.4 방사성폐기물의 정의 및 분류에 사용되는 기준

원자력법은 “방사성폐기물”을 방사성물질 또는 그에 의해서 오염된 물질로서

폐기의 대상이 되는 물질로 정의하고 있으며 사용후핵연료를 포함하고 있다. 원자

력법시행령은 방사성폐기물 중에서 방사능농도 및 열발생률이 특정값 이상인 폐기

물을 ‘고준위방사성폐기물’로 정의하고, 이에 해당되지 않는 방사성폐기물을 ‘중․저준위방사성폐기물’로 분류하고 있다. 방사능 농도와 열발생률의 정량적인 기준은

교육과학기술부고시 제2008-31호(방사선방호 등에 관한 기준 고시)에 다음과 같이

명시하고 있다.

- 방사능 : 반감기 20년 이상의 알파선을 방출하는 핵종으로 4,000 Bq/g 이상

- 열발생률 : 2 kW/m3 이상

1998년 이전까지 국내 방사성폐기물 분류체계는 액체 및 기체방사성폐기물의

방사능과 고체방사성폐기물의 표면 방사선량률을 기준으로 분류한 IAEA의

Technical Report Series No. 101 (1970)을 준용하였으나, 1998년 8월 11일 IAEA

Safety Series No.111-G-1.1 (1994)의 분류체계를 준용하여 위와 같이 방사성폐기물

의 처분안전성을 강조한 분류기준으로 개정한 것이다.

한편, IAEA 분류체계에 따른 규제면제폐기물 (Exempt Waste)은 “자체처분”이

라는 용어로 국내 원자력관계법령에 반영되었으며, “자체처분”에 대한 선량기준은

IAEA Safety Series No. 115 (1996)의 Clearance에 관한 선량기준 (개인에 대한 연

간선량이 10 µSv 미만이고 집단에 대한 총 선량이 1 person․Sv 미만)과 동일하게 적용하고 있다.

- 15 -

C. 적용범위 (제3조 )

공동협약 제 3 조 적용 범위

1. 이 협약은 사용후핵연료가 민수용 원자로의 운전에서 발생하는 경우 사용후핵연료

관리의 안전에 적용한다. 재처리 활동의 일부로서 재처리시설에 보관되어 있는 사

용후핵연료는 체약당사자가 재처리를 사용후핵연료 관리의 일부라고 선언하지 않

는 한 이 협약의 범위에서 제외된다.

2. 이 협약은 또한 민간의 사용과정에서 방사성폐기물이 발생하는 경우 방사성폐기물

관리의 안전에 적용한다. 그러나, 이 협약은, 폐기된 밀봉선원이 아니거나 체약당사자

에 의하여 이 협약의 목적에 맞는 방사성폐기물로 선언되지 않은 한, 단지 자연 발

생적인 방사성 물질만을 함유하고 핵연료 주기에서 발생되지 아니한 폐기물에

는 적용하지 아니한다.

3. 이 협약은 체약당사자에 의하여 이 협약의 목적에 맞는 사용후핵연료 또는 방사성

폐기물로 선언되지 않는 한 군사․방위 프로그램 내의 사용후핵연료 및 방사성폐

기물 관리의 안전에 적용하지 아니한다. 그러나 이 협약은 사용후핵연료 및 방사성

폐기물이 전적으로 민수용 프로그램 내로 영구히 이전되고 관리되는 경우에는 군

사․방위 프로그램에서 발생한 사용후핵연료 및 방사성폐기물의 관리 안전에 적용한다.

4. 이 협약은 또한 제4조, 제7조, 제11조, 제14조, 제24조 및 제26조에서 규정된 배출에

적용한다.

C.1 공동협약 적용 방사성폐기물

공동협약에 따른 본 보고서의 적용범위는 국내 원자력법령 및 관련 기술기준

에 의거하여 정의된 방사성폐기물이며 발전용 및 연구용 원자로시설에서 발생하는

사용후핵연료와 방사성폐기물, 핵연료주기시설에서 발생하는 방사성폐기물 그리고

방사성동위원소 등 이용기관에서 발생하는 방사성폐기물을 포함한다.

방사성폐기물의 정의 및 분류에 사용되는 법령과 기술기준은 본문 B.4에 기술

되어 있다.

- 16 -

C.2 사용후핵연료의 재처리

사용후핵연료에 관한 정부의 기본정책은 장기간 저장후 국내외 기술개발 추이

에 따라 추후 검토한 후 결정하게 되어 있다. 이에 따라 본 협약 제 3조 1항에 의

거 사용후핵연료의 재처리는 수행하고 있지 않으므로 본국가보고서에는 기술하지

않았다.

C.3 천연방사성물질

본 협약 제 3조 2항에 의거 핵연료주기시설 및 핵연료물질 사용시설에서 발생

한 천연방사성물질은 본 국가보고서에 포함하였다.

C.4 군사 ․ 방위시설 발생 방사성폐기물

본 협약 제 3조 3항에 의거 군사․방위시설에서 발생한 방사성폐기물을 본 보고서에서 기술하지 않았다. 그러나 군사․방위시설에서 발생한 방사성동위원소폐기물 중 방사성동위원소관리시설로 이관된 동위원소폐기물은 본 국가보고서의 저장량목

록에 포함 기술하였다.

- 17 -

D. 저장량 및 목록 (제32조 2항 )

공동협약 제 32 조 보고

2. 이 보고서는 다음을 포함한다.

가. 이 협약의 적용을 받는 사용후핵연료 관리시설의 목록, 위치, 주목적 및 주요 특성

나. 이 협약의 적용을 받는 저장중이거나 처분된 사용후핵연료의 재고량. 이 재고량은

물질에 대한 설명과 가능하면 질량 및 총 방사능에 관한 정보를 포함하여야 한다.

다. 이 협약의 적용을 받는 방사성폐기물 관리시설의 목록, 위치, 주목적 및 주요 특성

라. 이 협약의 적용을 받는 다음과 같은 방사성폐기물의 재고량

ㄱ. 방사성폐기물 관리 및 핵연료주기 시설에 저장중인 것

ㄴ. 처분된 것

ㄷ. 과거 관행에 의해 발생된 것.

이 재고량은 물질에 대한 설명 및 부피 또는 질량, 방사능 및 특정 핵종 등 입수

가능한 기타 적절한 정보를 포함한다.

마. 해체가 진행중인 원자력 시설의 목록과 해당 시설의 해체활동 상황

D.1 사용후핵연료 관리시설

D.1.1 발전시설

원자로에서 인출된 사용후핵연료는 일정기간 동안 호기별로 사용후핵연료

저장시설에 저장하고 있으며, 시설내 저장용량의 확장 및 호기간 이송을 통하여 저

장시설의 포화에 대비하고 있다. 부록 표 A-1은 각 발전소의 사용후핵연료 저장시

설의 위치 및 특성을 나타내고 있다.

2007년 12월말 현재 원자력발전소의 사용후핵연료 총 저장량은 경수로의 경

우 4,327.53 MTU이며, 중수로의 경우 5,092.33 MTU (건식저장 : 2,425.68, 습식저장

: 2,666.65) 이다. 발전용 원자로 사용후핵연료 저장량을 표 D.1-1에 제시하였다.

- 18 -

표 D.1-1 발전용 원자로 사용후핵연료 저장량 (2007. 12. 31 기준)

시설명 저장방식저장량

(MTU)

초기

최대농축도(w/o)원자로형

고리 발전소 습식 1,623.02 3.4 ~ 4.2 PWR

영광 발전소 습식 1,491.08 3.8 ~ 4.4 PWR

울진 발전소 습식 1,213.43 3.8 ~ 4.4 PWR

월성 발전소습식

건식

2,666.65

2,425.68천연우라늄 PHWR

D.1.2 연구시설

하나로 연구용 원자로

하나로는 다목적 연구용 원자로로서 핵연료 성능시험, 재료조사 시험, 방사성동위

원소 생산, 기초과학 및 응용연구에의 활용을 주목적으로 하여 여러 가지 연구개

발에 활용되고 있다.

하나로 사용후핵연료 저장수조는 내면을 스테인리스 강판으로 라이닝한 중량콘크

리트 구조물이다. 이 저장조는 하나로를 20년 간 정상 운전할 때 발생되는 사용

후핵연료뿐만 아니라 노심에 장전되어 있는 핵연료를 임시로 저장 할 수 있는 용

량을 가지고 있다. 하나로 사용후핵연료 저장수조의 위치 및 특성을 부록 표 A-2

에 제시하였다.

하나로에서 발생한 사용후핵연료의 종류 및 저장량을 표 D.1-2에 제시하였다.

조사후연료시험시설

조사후연료시험시설은 원자력발전소에서 연소된 사용후핵연료에 대한 성능시험

평가를 목적으로 건설되었다. 본 시설은 가압경수로형 사용후핵연료 집합체를

인수/하역/시험할 수 있는 수조시설, 연료봉을 시험할 수 있는 핫셀시설과 화

학분석시험시설을 갖추고 있다.

- 19 -

조사후연료시험시설은 3개의 수조와 4개의 콘크리트 핫셀, 2개의 납셀과 부대시

설로 구성되어 있다. 조사후연료시험시설 내 사용후핵연료 저장시설의 위치 및

시설의 특성을 부록 표 A-2에 제시하였다.

2007년 12월말 현재 조사후연료시험시설에는 조사후시험을 목적으로 국내 원전

에서 연소된 사용후핵연료가 집합체, 연료봉 및 시편의 상태로 저장되어 있다. 조

사후연료시험시설 내 저장하고 있는 사용후핵연료 저장량을 표 D.1-2에 제시하였

다.

시설명저장량

(MTU)

하나로 시설 0.52

조사후연료시험시설

(PIEF)3.27

표 D.1-2 연구시설 내 사용후핵연료 저장량 (2007. 12. 31 기준)

- 20 -

D.2 방사성폐기물 관리

D.2.1 발전시설

원자로 운영 중에 발생하는 방사성폐기물의 안전한 관리를 위해 기체, 액체

및 고체폐기물 처리시설과 소내 저장시설을 갖추고 있다. 기체폐기물처리시설은 기

체감쇠탱크 또는 활성탄 지연대로 구성되어 있으며, 액체폐기물처리계통은 폐액증

발기 또는 선택성이온교환기 등으로 구성되어있다. 고체폐기물처리계통은 폐수지

건조설비, 농축폐액 건조설비, 폐여과기 처리 및 포장설비, 압축기 등으로 구성되어

있다.

발전소 내에 위치하고 있는 방사성폐기물 저장시설은 콘크리트 슬라브 형태

의 건물이며 방사선준위에 따라 고체폐기물을 분류하여 저장하고 있다. 안전관리를

위하여 저장시설에는 방사선감시설비 등을 갖추고 있다. 원전부지내 방사성폐기물

저장시설 및 처리설비 현황은 부록 표 B-1 및 표 B-2에 수록되어있다.

발전용 원자로 시설에서 발생한 고체방사성폐기물은 2007년 12월말 현재 총

76,481 드럼으로 부지내 저장시설에 저장관리중이다. 2007년 12월말 현재 고체방사

성폐기물의 저장량과 주요핵종 및 총 방사능량은 표 D.2-1에 수록되어 있다.

표 D.2-1 발전용원자로 방사성폐기물 저장현황 (2007. 12. 31 기준)

시설명저장량

[200L 드럼]주요핵종

예상 총방사능

[TBq]

고리 발전소 37,977 Co-60, Cs-137 등 4.92E+2

월성 발전소 6,752 “ 9.75E+1

영광 발전소 18,246 “ 2.25E+2

울진 발전소 13,506 “ 4.06E+2

합계 76,481 “ 1.22E+3

- 21 -

D.2.2 연구시설

한국원자력연구원의 연구시설에서 발생하는 액체 및 고체폐기물을 안전하게

관리하기 위하여 방사성폐기물 처리시설 및 저장시설을 운영하고 있다. 방사성폐기

물 저장시설 및 처리시설 현황은 부록 표 B-3 및 표 B-4에 수록되어 있다.

시설에서 발생하는 액체폐기물은 증발 농축한 후 농축폐액은 아스팔트 고화

처리하여 저장시설에 보관하고 액체폐기물의 처리 후 발생되는 정제액과 극저준위

액체폐기물은 태양열 증발설비에서 처리하며, 고체폐기물은 저장 전에 압축과정을

거쳐 감용한 후 저장한다.

서울 공릉동에 위치하였던 구 한국원자력연구원에서 1985년 전에 발생된 방

사성폐기물을 200리터 드럼에 시멘트 고화 처리한 후, 1985년에 대전의 한국원자력

연구원으로 이송하여 방사성폐기물 저장시설에 저장․관리하고 있다.

2007년 12월 현재 한국원자력연구원 방사성 폐기물 저장고에 저장되어 있는

방사성폐기물의 저장량과 주요핵종 및 총 방사능량은 표 D.2-2에 수록되어있다.

시설명저장량

[200L 드럼]주요핵종

예상 총방사능

[TBq]

저장고 11,645Mn-54, Co-60, U-238

Cs-137, I-131 등1.3E+0

표 D.2-2 연구시설 방사성폐기물 저장현황 (2007. 12. 31 기준)

D.2.3 핵연료가공시설

핵연료 가공시설은 1989년에 운영이 시작된 제 1공장과 1998년에 운영을 시

작한 제 2공장 시설이 있다. 고체폐기물의 처리 및 저장 시설의 운영에 대한 기본

개념은 제 1공장 및 제 2공장이 동일하며 저장시설에 대한 자세한 사항은 부록 표

B-5에 제시 되어있다. 그리고 액체폐기물 처리시설은 발생되는 폐수의 특성에 따라

다르며 부록 표 B-6에 주요 특성이 제시되어 있다.

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핵연료 가공시설에서는 2007년 12월말 현재 6,661 드럼의 고체폐기물을 안

전하게 저장 관리하고 있으며, 저장량과 주요핵종 및 총 방사능량은 표 D.2-3에 수

록되어있다.

시설명저장량

[200L 드럼]주요핵종

예상 총방사능

[TBq]

저장고 6,661 U-234, U-235, U-238 2.9E-1

표 D.2-3 핵연료가공시설 방사성폐기물 저장현황 (2007. 12. 31 기준)

D.2.4 방사성동위원소 폐기물 관리시설

방사성동위원소이용시설에서 발생하는 방사성폐기물은 방사성동위원소 폐기

물 관리시설에 인도되어 저장된다. 방사성동위원소폐기물 관리시설에는 2007년 12

월말 현재 5,240드럼이 안전하게 저장중이며, 가연성 방사성폐기물을 처리하기 위

한 소각시설을 운영 중에 있다. 부록 표 B-7은 저장시설의 위치 및 주요특성을 보

여주고 있으며 부록 표 B-8은 운영 중인 소각시설에 대한 주요특성을 보여주고 있

다.

2007년 12월말 현재 방사성동위원소폐기물 관리시설에 저장중인 방사성동위

원소 폐기물에 대한 종류별 주요 핵종 및 총 방사능량은 표 D.2-4에 수록되어있다.

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시설명저장량

[200L 드럼]주요핵종

예상 총방사능

[TBq]

방사성

동위원소

폐기물

관리시설

5,018 (개봉선원) I-125, Tc-99m 등

2.9E+2

222 (밀봉선원) Co-60, Cs-137, Am-241 등

표 D.2-4 방사성동위원소 폐기물 저장현황 (2007. 12. 31 기준)